Simulation of the neutron flux in the irradiation facility at RA-3 reactor

Author:

Bortolussi S.,Pinto J.M.,Thorp S.I.,Farias R.O.,Soto M.S.,Sztejnberg M.,Pozzi E.C.C.,Gonzalez S.J.,Gadan M.A.,Bellino A.N.,Quintana J.,Altieri S.,Miller M.

Publisher

Elsevier BV

Subject

Radiation

Reference5 articles.

1. Miller, M., Quintana, J., Ojeda, J., Langan, S., Thorp, S., Pozzi, E., Sztejnberg, M., Estryk, G., Nosal, R., Saire, E., Agrazar, H., Graiño, F., 2008. New irradiation facility for biomedical applications at the RA-3 reactor thermal column. In: Proceedings of the 13th ICNCT, pp. 379–382.

2. Implantable self-powered detector for on-line determination of neutron flux in patients during NCT treatment;Miller;Appl. Radiat. Isot.,2004

3. Soto, M.S., González, S.J., Thorp, S.I., Pozzi, E.C.C., Farías, R.O., Gadan, M.A., Miller, M.E., 2009. Characterization and optimization of the RA-3 preliminary dosimetry for the radiotolerance study of the normal sheep lung. In: Proceedings of the Young Researchers Boron Neutron Capture Therapy Meeting, Mainz, Germany.

4. X-5 Monte Carlo Team, 2005. MCNP—a general Monte Carlo N-Particle transport code, version 5, vols. 1–3, LA-UR-031987, LA-CP-03-0245, and LA-CP-03-0284, Los Alamos National Laboratory, New Mexico, USA.

5. Extra-corporeal liver BNCT for the treatment of diffuse metastases: what was learned and what is still to be learned;Zonta;Appl. Radiat. Isot.,2009

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